Subjects -> ENERGY (Total: 414 journals)
    - ELECTRICAL ENERGY (12 journals)
    - ENERGY (252 journals)
    - ENERGY: GENERAL (7 journals)
    - NUCLEAR ENERGY (40 journals)
    - PETROLEUM AND GAS (58 journals)
    - RENEWABLE ENERGY (45 journals)

NUCLEAR ENERGY (40 journals)

Showing 1 - 37 of 37 Journals sorted alphabetically
Atom Indonesia     Open Access  
Bulletin of the Atomic Scientists     Hybrid Journal   (Followers: 8)
CNL Nuclear Review     Partially Free  
Eksplorium : Buletin Pusat Pengembangan Bahan Galian Nuklir     Open Access  
EPJ Nuclear Sciences & Technologies     Open Access   (Followers: 3)
Fusion Science and Technology     Hybrid Journal   (Followers: 4)
Ganendra : Majalah IPTEK Nuklir     Open Access  
Hyperfine Interactions     Hybrid Journal   (Followers: 1)
IEEE Transactions on Sustainable Energy     Hybrid Journal   (Followers: 13)
International Journal of Advanced Nuclear Reactor Design and Technology     Open Access  
International Journal of Critical Infrastructure Protection     Hybrid Journal   (Followers: 4)
International Journal of Nuclear Energy Science and Engineering     Open Access   (Followers: 5)
International Journal of Nuclear Law     Hybrid Journal   (Followers: 3)
International Journal of Nuclear Safety and Security     Hybrid Journal   (Followers: 1)
International Journal of Nuclear Security     Open Access   (Followers: 1)
Journal of Nuclear Energy Science & Power Generation Technology     Hybrid Journal   (Followers: 2)
Journal of Nuclear Engineering & Technology     Full-text available via subscription   (Followers: 3)
Journal of Nuclear Science and Technology     Hybrid Journal   (Followers: 2)
Journal of Power Technologies     Open Access   (Followers: 6)
Journal of Radiation Research     Open Access   (Followers: 3)
Journal of the Physical Society of Japan     Hybrid Journal   (Followers: 2)
Kerntechnik     Full-text available via subscription  
Majalah Ilmiah Teknologi Elektro : Journal of Electrical Technology     Open Access   (Followers: 1)
Nano Energy     Open Access   (Followers: 11)
Nanomaterials and Energy     Hybrid Journal   (Followers: 1)
Nuclear Energy and Technology     Open Access   (Followers: 3)
Nuclear Engineering and Technology     Open Access   (Followers: 5)
Nuclear Materials and Energy     Open Access   (Followers: 1)
Nuclear Science and Engineering     Hybrid Journal   (Followers: 7)
Nuclear Science and Techniques     Full-text available via subscription  
Nuclear Technology     Hybrid Journal   (Followers: 5)
Nucleus     Open Access  
Nukleonika     Open Access  
Radiation Detection Technology and Methods     Hybrid Journal   (Followers: 1)
Tri Dasa Mega : Jurnal Teknologi Reaktor Nuklir     Open Access  
Urania Jurnal Ilmiah Daur Bahan Bakar Nuklir     Open Access  
World Journal of Nuclear Science and Technology     Open Access   (Followers: 4)
Similar Journals
Journal Cover
Nuclear Science and Engineering
Journal Prestige (SJR): 0.92
Citation Impact (citeScore): 1
Number of Followers: 7  
 
Hybrid Journal Hybrid journal   * Containing 21 Open Access Open Access article(s) in this issue *
ISSN (Print) 0029-5639 - ISSN (Online) 1943-748X
Published by Taylor and Francis Homepage  [2652 journals]
  • The Virtual Test Bed (VTB) Repository: A Library of Reference Reactor
           Models Using NEAMS Tools

         This is an Open Access Article Open Access Article

    • Free pre-print version: Loading...

      Authors: Guillaume L. Giudicelli, Abdalla Abou-Jaoude, April J. Novak, Ahmed Abdelhameed, Paolo Balestra, Lise Charlot, Jun Fang, Bo Feng, Thomas Folk, Ramiro Freile, Thomas Freyman, Derek Gaston, Logan Harbour, Thanh Hua, Wen Jiang, Nicolas Martin, Yinbin Miao, Jason Miller, Isaac Naupa, Dan O’Grady, David Reger, Emily Shemon, Nicolas Stauff, Mauricio Tano, Stefano Terlizzi, Samuel Walker, Cody Permann
      Pages: 1 - 17
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-23T08:11:19Z
      DOI: 10.1080/00295639.2022.2142440
       
  • Thermal-Hydraulic Investigation of Steady-State Single-Phase Natural
           Circulation of an Integral PWR-Type SMR Test Rig (iPSTR)

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      Authors: Muhammad Ishaq, Muhammad Ilyas, Alam Nawaz Khan Wardag, Muhammad Zaman, Mansoor H. Inayat
      Pages: 1 - 29
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-23T02:11:07Z
      DOI: 10.1080/00295639.2022.2139565
       
  • Post-Neutron Mass Yield Distribution in the Epi-Cadmium Neutron Induced
           Fission of 229Th

    • Free pre-print version: Loading...

      Authors: H. Naik, R. J. Singh, S. P. Dange, W. Jang
      Pages: 1 - 14
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-23T02:08:42Z
      DOI: 10.1080/00295639.2022.2150029
       
  • Influence of Quantum Oscillations in the Thermal Scattering Law of
           Zirconium Carbide on Neutron Thermalization and Criticality

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      Authors: J. L. Wormald, J. C. Holmes, M. L. Zerkle
      Pages: 1 - 14
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-23T02:04:50Z
      DOI: 10.1080/00295639.2022.2138063
       
  • Discrete-Time Bayesian Networks Applied to Flexible Coping Strategies of
           Nuclear Power Plant Systems

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      Authors: Elvan Sahin, Victor C. Leite, Kyung M. Kim, Nick Burns, Juliana Pacheco Duarte
      Pages: 1 - 18
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-19T05:30:28Z
      DOI: 10.1080/00295639.2022.2151300
       
  • Thermal-Hydraulic Analysis of the AFIP-7 Irradiation Test in the Advanced
           Test Reactor—Oxide Growth Prediction and Correlation

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      Authors: Changhu Xing, Casey J. Jesse, Warren F. Jones, Maxine P. Johnson, Ann Marie Phillips, Theron D. Marshall
      Pages: 1 - 12
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-19T05:29:28Z
      DOI: 10.1080/00295639.2022.2153599
       
  • Application of Accelerator Beam Dumps for Dark Matter Searches

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      Authors: Patrick Achenbach, Mirco Christmann
      Pages: 1 - 6
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-19T05:28:29Z
      DOI: 10.1080/00295639.2022.2151301
       
  • A Generalized Eigenvalue Formulation for Core-Design Applications

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      Authors: Nicolo’ Abrate, Sandra Dulla, Piero Ravetto, Paolo Saracco
      Pages: 1 - 25
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-17T01:15:34Z
      DOI: 10.1080/00295639.2022.2134685
       
  • myMUSCLE, a New Multiphysics, Multiscale Simulation Coupling Environment

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      Authors: H. J. Uitslag-Doolaard, K. Zwijsen, F. Roelofs, M. M. Stempniewicz
      Pages: 1 - 18
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-12T01:24:21Z
      DOI: 10.1080/00295639.2022.2148809
       
  • Analyses of Critical Hydrogen Enrichment in PWR Containment Compartments

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      Authors: E. Schmidt, N. Reinke, M. Freitag, M. Sonnenkalb
      Pages: 1 - 13
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-12T01:20:35Z
      DOI: 10.1080/00295639.2022.2146994
       
  • A Quasi–Monte Carlo Method With Krylov Linear Solvers for Multigroup
           Neutron Transport Simulations

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      Authors: Sam Pasmann, Ilham Variansyah, C. T. Kelley, Ryan McClarren
      Pages: 1 - 15
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-12T01:19:53Z
      DOI: 10.1080/00295639.2022.2143704
       
  • State of the Art in Cyclotrons for Radionuclide Production in Biomedicine

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      Authors: Mario Marengo, Gianfranco Cicoria, Angelo Infantino, Sara Vichi, Federico Zagni, Domiziano Mostacci
      Pages: 1 - 11
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-11T02:57:51Z
      DOI: 10.1080/00295639.2022.2146433
       
  • Geometry Extension and Assemblywise Domain Decomposition of nTRACER for
           Direct Whole-Core Calculation of VVERs

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      Authors: Seongchan Kim, Han Gyu Joo
      Pages: 1 - 20
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-11T02:56:05Z
      DOI: 10.1080/00295639.2022.2144083
       
  • Multiphysics Analysis System for Heat Pipe Cooled Micro Reactors Employing
           PRAGMA-OpenFOAM-ANLHTP

    • Free pre-print version: Loading...

      Authors: Jaeuk Im, Myung Jin Jeong, Namjae Choi, Kyung Min Kim, Hyoung Kyu Cho, Han Gyu Joo
      Pages: 1 - 15
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-11T02:55:51Z
      DOI: 10.1080/00295639.2022.2143209
       
  • Post-Neutron Mass Yield Distribution in the Thermal Neutron Induced
           Fission of 233U

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      Authors: H. Naik, S. P. Dange, R. J. Singh, W. Jang
      Pages: 1 - 26
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-11T02:52:46Z
      DOI: 10.1080/00295639.2022.2142433
       
  • Review of the Fluid Dynamics and Heat Transport Phenomena in Packed Pebble
           Bed Nuclear Reactors

         This is an Open Access Article Open Access Article

    • Free pre-print version: Loading...

      Authors: Rahman S. Almusafir, Ahmed A. Jasim, Muthanna H. Al-Dahhan
      Pages: 1 - 37
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-10T01:40:23Z
      DOI: 10.1080/00295639.2022.2146993
       
  • Wigner-Wilkins Neutron/Nucleus Scattering Kernel Quantum Mechanically
           Derived

         This is an Open Access Article Open Access Article

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      Authors: J. A. Grzesik
      Pages: 1 - 9
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-10T01:38:56Z
      DOI: 10.1080/00295639.2022.2138064
       
  • Nonconforming Three-Dimensional Model for PWR Control Rod Movements
           Without Homogenization and Cusping Effect

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      Authors: F. Filiciotto, E. Masiello, S. Cochet-Lapuerta, R. Lenain
      Pages: 1 - 21
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-09T03:23:12Z
      DOI: 10.1080/00295639.2022.2151783
       
  • A Novel Core Design with Movable Moderator for a Fluoride
           Salt–Cooled High-Temperature Reactor

         This is an Open Access Article Open Access Article

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      Authors: Zuolong Zhu, Dean Wang, Valmor de Almeida, Charles Forsberg, Eugene Shwageraus
      Pages: 1 - 16
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-05T03:36:39Z
      DOI: 10.1080/00295639.2022.2146436
       
  • Study of Reactor Core Loading Monitoring at the GUINEVERE Facility

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      Authors: A. Bailly, J.-L. Lecouey, A. Billebaud, S. Chabod, A. Kochetkov, A. Krása, F.-R. Lecolley, G. Lehaut, N. Marie, N. Messaoudi, G. Vittiglio, J. Wagemans
      Pages: 1 - 11
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2023-01-05T02:40:30Z
      DOI: 10.1080/00295639.2022.2148813
       
  • Technical Reviewers

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      Abstract: Volume 197, Issue 1, JANUARY 2023, Page iii-v
      .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-12-12T07:37:39Z
      DOI: 10.1080/00295639.2023.2156210
      Issue No: Vol. 197, No. 1 (2022)
       
  • Feynman-α Analysis Using BGO Gamma-Ray Detector in a University
           Training and Research Reactor

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      Authors: Masaki Goto, Tadafumi Sano, Kunihiro Nakajima, Takashi Kanda, Atsushi Sakon, Kengo Hashimoto
      Pages: 1 - 9
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-12-22T07:12:15Z
      DOI: 10.1080/00295639.2022.2143707
       
  • Numerical Investigation on the Thermal-Hydraulic Characteristics near a
           Corroded Lower Head of the Reactor Vessel During IVR-ERVC

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      Authors: Cheng Peng, Youya Song, Jian Deng, Sen Mao, Jiang Wu
      Pages: 1 - 16
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-12-21T04:37:56Z
      DOI: 10.1080/00295639.2022.2143208
       
  • Capability Extension of the High-Resolution Thermal-Hydraulic Code ESCOT
           for Hexagonal Geometry Core Multiphysics Analysis

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      Authors: Jorge Gonzalez-Amoros, Marianna Papadionysiou, Seongchan Kim, Han Gyu Joo
      Pages: 1 - 22
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-12-21T04:36:07Z
      DOI: 10.1080/00295639.2022.2140577
       
  • Post-Neutron Mass Yield Distribution in the Thermal Neutron Induced
           Fission of 235U

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      Authors: H. Naik, S. P. Dange, R. J. Singh, W. Jang
      Pages: 1 - 25
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-12-21T04:35:57Z
      DOI: 10.1080/00295639.2022.2133947
       
  • High-Fidelity Neutron Transport Solution of High Temperature Gas-Cooled
           Reactor by Three-Dimensional Linear Source Method of Characteristics

    • Free pre-print version: Loading...

      Authors: Kaijie Zhu, Boran Kong, Han Zhang, Jiong Guo, Fu Li
      Pages: 1 - 23
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-12-16T02:34:54Z
      DOI: 10.1080/00295639.2022.2143706
       
  • Euler-Euler Model of Bubbly Flow Using Particle-Center-Averaging Method

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      Authors: Hongmei Lyu, Fabian Schlegel, Roland Rzehak, Dirk Lucas
      Pages: 1 - 18
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-12-16T02:32:09Z
      DOI: 10.1080/00295639.2022.2131344
       
  • Deep Subcriticality Determination Using the Source Jerk Integral Method in
           the SALMON Program

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      Authors: A. Kochetkov, A. Krása, N. Messaoudi, G. Vittiglio, J. Wagemans, A. Bailly, A. Billebaud, S. Chabod, F. -R. Lecolley, J. -L. Lecouey, G. Lehaut, N. Marie
      Pages: 1 - 9
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-12-16T02:31:24Z
      DOI: 10.1080/00295639.2022.2146429
       
  • Pressurized Water Reactor Core Power Control Using BAS-RBF-PID Approach
           During Transient Operation

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      Authors: Derjew Ayele Ejigu, Xiaojing Liu
      Pages: 1 - 16
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-12-16T02:27:57Z
      DOI: 10.1080/00295639.2022.2138688
       
  • Parametric Model-Order Reduction for Radiation Transport Simulations Based
           on an Affine Decomposition of the Operators

         This is an Open Access Article Open Access Article

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      Authors: Patrick Behne, Jan Vermaak, Jean Ragusa
      Pages: 1 - 29
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-12-15T08:10:29Z
      DOI: 10.1080/00295639.2022.2112901
       
  • Computational Fluid Dynamics Analysis of an Open-Pool Nuclear Research
           Reactor Core for Fluid Flow Optimization Using a Channel Box

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      Authors: N. L. Scuro, G. Angelo, E. Angelo, M. H. A. Piro, P. E. Umbehaun, W. M. Torres, D. A. Andrade
      Pages: 1 - 17
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-12-15T08:10:17Z
      DOI: 10.1080/00295639.2022.2142437
       
  • Variance Reduction and Noise Source Sampling Techniques for Monte Carlo
           Simulations of Neutron Noise Induced by Mechanical Vibrations

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      Authors: Hunter Belanger, Davide Mancusi, Amélie Rouchon, Andrea Zoia
      Pages: 1 - 24
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-12-09T05:05:46Z
      DOI: 10.1080/00295639.2022.2126719
       
  • Numerical Simulation of Sub-cooled Flow Boiling in a Vertical Annulus
           Channel Under Near Atmospheric Pressure Conditions

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      Authors: Sachin Tom, P. Mangarjuna Rao, B. Venkatraman, S. Raghupathy
      Pages: 1 - 33
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-12-09T02:32:22Z
      DOI: 10.1080/00295639.2022.2133948
       
  • Introduction of the Adding and Doubling Method for Solving Bateman
           Equations for Nuclear Fuel Depletion

         This is an Open Access Article Open Access Article

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      Authors: Olin W. Calvin, Barry D. Ganapol, R. A. Borrelli
      Pages: 1 - 31
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-12-09T02:30:07Z
      DOI: 10.1080/00295639.2022.2129950
       
  • Using a Random Forest Model to Choose Optimized Group Structures

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      Authors: Thomas G. Saller, Vishnu Nair, Andrew Till, Nathan Gibson
      Pages: 1 - 19
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-12-09T02:29:27Z
      DOI: 10.1080/00295639.2022.2133940
       
  • Variable Dynamic Mode Decomposition For Estimating Time Eigenvalues in
           Nuclear Systems

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      Authors: Ethan Smith, Ilham Variansyah, Ryan McClarren
      Pages: 1 - 10
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-12-06T03:52:33Z
      DOI: 10.1080/00295639.2022.2142025
       
  • Compensated Feed water Pump Control Analysis of Effect of Base-Load
           Electricity Demand Reduction on Nuclear Steam Supply System

         This is an Open Access Article Open Access Article

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      Authors: Frederick Agyemang, Stephen Yamoah, Seth Kofi Debrah
      Pages: 1 - 12
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-12-05T07:21:01Z
      DOI: 10.1080/00295639.2022.2132102
       
  • An Improved Dual Asymmetric Penalized Least Squares Baseline Correction
           Method for High-Noise Spectral Data Analysis

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      Authors: Shuangbao Shu, Ziqiao Yu, Jiaxin Zhang, Zhiqiang Chen, Huajun Liang, Jingjing Chen
      Pages: 1 - 12
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-21T03:55:24Z
      DOI: 10.1080/00295639.2022.2132101
       
  • OpenFOAM-Hybrid: A Morphology Adaptive Multifield Two-Fluid Model

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      Authors: Fabian Schlegel, Richard Meller, Benjamin Krull, Ronald Lehnigk, Matej Tekavčič
      Pages: 1 - 14
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-21T03:53:20Z
      DOI: 10.1080/00295639.2022.2120316
       
  • Core Concept of Small Rotational Fuel-Shuffling Breed-and-Burn Fast
           Reactor with Nitride Fuel and Sodium Coolant

         This is an Open Access Article Open Access Article

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      Authors: Tsendsuren Amarjargal, Jun Nishiyama, Toru Obara
      Pages: 1 - 8
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-18T03:34:02Z
      DOI: 10.1080/00295639.2022.2129952
       
  • State-of-the-Art in Evaluation Approaches for Risk Assessment of Insider
           Threats to Nuclear Facility Physical Protection Systems

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      Authors: Chris Faucett, Karen Vierow Kirkland
      Pages: 1 - 12
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-18T03:34:01Z
      DOI: 10.1080/00295639.2022.2130635
       
  • Convergence Properties of a Linear Diffusion-Acceleration Method for
           k-Eigenvalue Transport Problems

         This is an Open Access Article Open Access Article

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      Authors: Anthony P. Barbu, Marvin L. Adams
      Pages: 1 - 17
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-18T03:33:08Z
      DOI: 10.1080/00295639.2022.2123205
       
  • Physics-Informed Neural Network Method and Application to Nuclear Reactor
           Calculations: A Pilot Study

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      Authors: Mohamed H. Elhareef, Zeyun Wu
      Pages: 1 - 22
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-15T07:36:14Z
      DOI: 10.1080/00295639.2022.2123211
       
  • Experimental Analysis of Fast-Transient Flow Boiling in Various Flow
           Conditions Using Inverse Heat Conduction Calculation Method

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      Authors: Yong-Seok Choi, Dong-Hoon Kam, Byong-Guk Jeon, Jong-Kuk Park, Sang-Ki Moon
      Pages: 1 - 12
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-15T07:35:44Z
      DOI: 10.1080/00295639.2022.2132100
       
  • Investigation of the Inhomogeneous Mechanical and Crack Driving Force of
           Low Alloy Steel SA508 and Its Welded 309L/308L Stainless Steel Cladding

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      Authors: Shuai Wang, He Xue, Guiyi Wu, Zheng Wang, Kuan Zhao, Chenqiang Ni
      Pages: 1 - 10
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-15T07:33:32Z
      DOI: 10.1080/00295639.2022.2123210
       
  • Correction

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      Pages: 1 - 1
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-15T07:29:08Z
      DOI: 10.1080/00295639.2022.2112897
       
  • LQG/LTR Controller Design for Power Control of Small Pressurized Water
           Reactors Under Four Feedback-Controlled Strategies

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      Authors: Shifa Wu, Jiashuang Wan, Zhi Chen, Longtao Liao, Kai Xiao, Pengfei Wang
      Pages: 1 - 16
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-14T03:01:52Z
      DOI: 10.1080/00295639.2022.2123204
       
  • Analysis of Integral Experiment of the AHWR Critical Facility with
           Diffusion based Monte Carlo Method

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      Authors: Argala Srivastava, Deep Bhandari, K. P. Singh, Umasankari Kannan
      Pages: 1 - 8
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-04T08:18:39Z
      DOI: 10.1080/00295639.2022.2131343
       
  • Mixcoatl Software (Part 2): Verification of 1D Fluid Flow Methods Coupled
           to 3D FEM Thermal Diffusion Models

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      Authors: Ross Pivovar, Rebecca Owston
      Pages: 1 - 17
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-04T08:17:52Z
      DOI: 10.1080/00295639.2022.2126718
       
  • Radiolytic Production of Fluorine Gas from MSR Relevant Fluoride Salts

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      Authors: Lance Davis, Ralph Hania, Dennis Boomstra, Dillon Rossouw, Florence Charpin-Jacobs, Jan Uhlir, Martin Maracek, Helmut Beckers, Sebastian Riedel
      Pages: 1 - 14
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-04T08:17:01Z
      DOI: 10.1080/00295639.2022.2129951
       
  • Possible Does Not Mean Useful: The Role of Probability of Attack in
           Security Risk Management

         This is an Open Access Article Open Access Article

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      Authors: Gregory D. Wyss, Adam D. Williams
      Pages: 1 - 15
      Abstract: .

      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-04T08:16:35Z
      DOI: 10.1080/00295639.2022.2129224
       
  • Effects of Vent Size and Wind on Dispersion of Hydrogen Leaked in a
           Partially Open Space: Studies by Numerical Analysis

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      Authors: Atsuhiko Terada, Ryuji Nagaishi
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-04T03:43:52Z
      DOI: 10.1080/00295639.2022.2126689
       
  • Bayesian Estimation of Cross-Section, Experimental Error, and Calculation
           Error: Comparison with Bias Factor Method

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      Authors: Satoshi Takeda, Takanori Kitada
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-03T11:01:50Z
      DOI: 10.1080/00295639.2022.2123679
       
  • An Analysis of Transport Effects in Steady-State Simulation of the Molten
           Salt Reactor Experiment

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      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-02T05:59:53Z
      DOI: 10.1080/00295639.2022.2097565
       
  • Quantification of Deep Neural Network Prediction Uncertainties for VVUQ of
           Machine Learning Models

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      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-02T05:57:58Z
      DOI: 10.1080/00295639.2022.2123203
       
  • The NILO-CMFD Method for Iteratively Solving Coupled Neutron
           Transport–Thermal Hydraulics Problems

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      Authors: Nickolas J. Adamowicz, Annalisa Manera, Edward W. Larsen
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-01T07:09:52Z
      DOI: 10.1080/00295639.2022.2112900
       
  • A Limited-Memory Framework for Conditional Point Sampling for Radiation
           Transport in 1D Stochastic Media

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      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-01T07:08:51Z
      DOI: 10.1080/00295639.2022.2116378
       
  • New Security Concepts for Advanced Reactors
         This is an Open Access Article Open Access Article

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      Authors: Alan Evans, John L. Russell, Benjamin B. Cipiti
      Pages: 1 - 10
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-11-01T07:08:46Z
      DOI: 10.1080/00295639.2022.2112134
       
  • A Dynamic Risk Framework for the Physical Security of Nuclear Power Plants
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-10-12T03:07:11Z
      DOI: 10.1080/00295639.2022.2112899
       
  • Flow-Induced Vibrations of Two Flexible Tubes in Cross Flow

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      Pages: 1 - 15
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-10-05T02:53:57Z
      DOI: 10.1080/00295639.2022.2118478
       
  • Hybrid Variable Selection for Estimating Nominal HEPs and PIF Multipliers
           for Digital Control Rooms

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      Authors: Yochan Kim, Jinkyun Park, Mary Presley
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-10-04T06:28:41Z
      DOI: 10.1080/00295639.2022.2118481
       
  • An Inline Burnup Algorithm
         This is an Open Access Article Open Access Article

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      Authors: P. Cosgrove, E. Shwageraus, J. Leppänen
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-10-04T06:28:10Z
      DOI: 10.1080/00295639.2022.2106732
       
  • Numerical Caseology by Lagrange Interpolation for the 1D Neutron Transport
           Equation in a Slab

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      Authors: B.D. Ganapol
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-10-04T06:26:13Z
      DOI: 10.1080/00295639.2022.2097494
       
  • Measurements of the 27Al(α,n) Thick Target Yield near Threshold

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      Authors: K. Brandenburg, G. Hamad, Z. Meisel, C. R. Brune, D. E. Carter, J. Derkin, D. C. Ingram, Y. Jones-Alberty, B. Kenady, T. N. Massey, M. Saxena, D. Soltesz, S. K. Subedi, J. Warren
      Pages: 1 - 7
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-10-03T09:27:05Z
      DOI: 10.1080/00295639.2022.2118483
       
  • Methods for Calculating Neutron Transfer Probabilities Between Assemblies

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      Authors: Patrick F. O’Rourke, Anil K. Prinja
      Pages: 1 - 9
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-10-03T08:50:05Z
      DOI: 10.1080/00295639.2022.2106728
       
  • Computing Physical Security System Effectiveness at Commercial Reactors
         This is an Open Access Article Open Access Article

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      Authors: Matthew Talbot, Dan McCorquodale, Ian Broglie
      Pages: 1 - 11
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-10-03T08:48:01Z
      DOI: 10.1080/00295639.2022.2120315
       
  • A CFD Modeling Coupled with VOF Method and Solidification Model for Molten
           Jet Breakup at Low Velocity

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      Authors: Tao Liu, Yuan Zhou, Mingjun Zhong, Houjun Gong
      Pages: 1 - 15
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-09-28T05:30:46Z
      DOI: 10.1080/00295639.2022.2116379
       
  • Improvements in Antineutrino Spectrum by Including Fission Product
           Corrections and Calculation of Scatter-based Pulse Height Distributions

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      Authors: Wei Eng Ang, Sanghun Lee, Shikha Prasad
      Pages: 1 - 20
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-09-28T05:28:56Z
      DOI: 10.1080/00295639.2022.2103348
       
  • Computational Analysis of Thermal Striping in Primary Sodium System of
           Liquid Metal Fast Breeder Reactor Using Finite Volume Method

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      Authors: S. Suyambazhahan, T. Sundararajan, Sarit K. Das
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-09-26T12:48:11Z
      DOI: 10.1080/00295639.2022.2116380
       
  • Monte Carlo Source Convergence Acceleration by Hybrid Multi-group and
           Continuous Energy Neutron Transport

         This is an Open Access Article Open Access Article

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      Authors: Valeria Raffuzzi, Eugene Shwageraus, Lee Morgan, Paul Cosgrove
      Pages: 1 - 17
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-09-12T07:23:58Z
      DOI: 10.1080/00295639.2022.2107262
       
  • A Multigroup Homogeneous Flux Reconstruction Method Based on the
           ANOVA-HDMR Decomposition

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      Authors: Pavel M. Bokov, Danniell Botes, Rian H. Prinsloo, Djordje I. Tomašević
      Pages: 1 - 25
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-09-09T01:50:16Z
      DOI: 10.1080/00295639.2022.2108654
       
  • Development, Verification, and Validation of an Advanced Systems Code
           KP-SAM for Kairos Power Fluoride Salt-Cooled High-Temperature Reactor
           (KP-FHR)

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      Authors: Haihua Zhao, Lambert Fick, Alexander Heald, Quan Zhou, Samuel Richesson, Noah Sutton, Brandon Haugh
      Pages: 1 - 27
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-09-09T01:50:08Z
      DOI: 10.1080/00295639.2022.2106724
       
  • Simulation of the High Temperature Test Facility (HTTF) Core Using the 2D
           Ring Model with SAM

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      Authors: Zhiee Jhia Ooi, Thanh Hua, Ling Zou, Rui Hu
      Pages: 1 - 28
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-09-08T07:22:14Z
      DOI: 10.1080/00295639.2022.2106726
       
  • Identifying Thermodynamic Mechanisms Affecting Reactor Pressure Vessel
           Integrity During Severe Nuclear Accidents Simulated by Laser Heating at
           the Laboratory Scale

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      Authors: Michail Athanasakis-Kaklamanakis, Dario Manara, Luka Vlahovic, Davide Robba, Konstantinos Boboridis, Markus Ernstberger, Rachel Eloirdi, Pedro Amador, Rudy J. M. Konings
      Pages: 1 - 17
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-09-08T07:09:01Z
      DOI: 10.1080/00295639.2022.2108643
       
  • A Perspective on Data-Driven Coarse Grid Modeling for System Level Thermal
           Hydraulics

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      Authors: Arsen S. Iskhakov, Cheng-Kai Tai, Igor A. Bolotnov, Nam T. Dinh
      Pages: 1 - 16
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-09-08T07:08:01Z
      DOI: 10.1080/00295639.2022.2107864
       
  • Simulation of the Axial-Flow Centrifugal Bubble Separator for
           Liquid-Fueled Molten Salt Reactors Using Eulerian Two-Fluid Model

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      Authors: Jiaqi Chen, Caleb S. Brooks
      Pages: 1 - 21
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-09-08T01:12:02Z
      DOI: 10.1080/00295639.2022.2103347
       
  • A Unified Framework of Stabilized Finite Element Methods for Solving the
           Boltzmann Transport Equation

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      Authors: Qingming He, Chao Fang, Liangzhi Cao, Haoyu Zhang
      Pages: 1 - 13
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-09-07T06:00:38Z
      DOI: 10.1080/00295639.2022.2106733
       
  • Simulation of the Melting Behavior of the UO2-Zircaloy Fuel Cladding
           System by Laser Heating

         This is an Open Access Article Open Access Article

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      Authors: L. Soldi, D. Manara, D. Bottomley, D. Robba, L. Luzzi, R. J. M. Konings
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-09-07T06:00:25Z
      DOI: 10.1080/00295639.2022.2106731
       
  • Post-Neutron Fission Product Yield Distribution in the Spontaneous Fission
           of 244Cm

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      Authors: H. Naik, R. J. Singh, W. Jang
      Pages: 1 - 20
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-09-06T05:16:02Z
      DOI: 10.1080/00295639.2022.2103345
       
  • Numerical Investigations of Molten Salt Pump Journal Bearings Under
           Hydrodynamic Lubrication Conditions for FHRs

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      Authors: Yuqi Liu, Shuai Che, Adam Burak, Daniel L. Barth, Nicolas Zweibaum, Minghui Chen
      Pages: 1 - 13
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-08-30T08:22:11Z
      DOI: 10.1080/00295639.2022.2103343
       
  • Uncertainty Quantification of a Light Water Pulsed-Neutron Die-Away
           Experiment to Thermal Neutron Scattering Laws

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      Authors: Daniel Siefman, Mathieu Hursin, Catherine Percher, David Heinrichs
      Pages: 1 - 11
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-08-30T08:21:48Z
      DOI: 10.1080/00295639.2022.2103344
       
  • Beta-Ray-Bremsstrahlung Contributions to Short-Lived Delayed Photoneutron
           Groups in Heavy Water Reactors

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      Authors: Yanuar Ady Setiawan, Hemantika Sengar, Douglas A. Fynan, Arief Rahman Hakim
      Pages: 1 - 21
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-08-30T08:19:55Z
      DOI: 10.1080/00295639.2022.2103341
       
  • Thermal-Hydraulic System-Level Analysis of a Molten Salt Natural
           Circulation Loop

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      Authors: Sheng Zhang, Hsun-Chia Lin, Xiaodong Sun
      Pages: 1 - 27
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-08-25T02:15:41Z
      DOI: 10.1080/00295639.2022.2102389
       
  • A Stochastic Transport Model for the Cumulative Number of Fissions and
           Deposited Fission Energy

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      Authors: Anil K. Prinja, Patrick F. O’Rourke
      Pages: 1 - 23
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-08-25T02:07:05Z
      DOI: 10.1080/00295639.2022.2087830
       
  • Infiltration and Evaporation in Multiplying Porous Media and Associated
           Criticality Phenomena

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      Authors: M. M. R. Williams
      Pages: 1 - 28
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-08-22T02:43:41Z
      DOI: 10.1080/00295639.2022.2103336
       
  • Development of an Activity Transport Model and in situ Measurements on
           Deposited Radionuclides in the Primary Coolant Pipelines of the Chinshan
           Nuclear Power Plant

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      Authors: Yu-Hung Shih, Mei-Ya Wang, Tsuey-Lin Tsai, Tsung-Kuang Yeh
      Pages: 1 - 12
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-08-22T02:38:28Z
      DOI: 10.1080/00295639.2022.2102392
       
  • Comparisons of Supercritical Loop Flow and Heat Transfer Behavior Under
           Uniform and Nonuniform High-Flux Heat Inputs

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      Authors: Dong Yang, Lin Chen, Yongchang Feng, Haisheng Chen
      Pages: 1 - 18
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-08-16T03:15:07Z
      DOI: 10.1080/00295639.2022.2102391
       
  • Effect of Internal Decay Power and Surface Cooling on Nuclear Fuel Droplet
           Solidification during MFCI in a SFR – A Numerical Study

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      Authors: M. Chandra Kumar, A. Jasmin Sudha, V. Subramanian, S. Athmalingam, B. Venkatraman
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-08-16T03:10:20Z
      DOI: 10.1080/00295639.2022.2103338
       
  • Informing Performance Metrics of Advanced I&C Systems for Liquid Fueled
           Fast Molten Salt Reactors

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      Authors: Yeongshin Jeong, Koroush Shirvan, Michael Buric
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-08-05T05:02:16Z
      DOI: 10.1080/00295639.2022.2102388
       
  • Design and Thermal-Hydraulic Performance Analysis of a Low-Temperature
           Heat Pipe Test Facility

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      Authors: Ilyas Yilgor, Eymon Lan, Shanbin Shi
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-08-01T02:32:00Z
      DOI: 10.1080/00295639.2022.2087835
       
  • Validation and Uncertainty Quantification of Transient Reflood Models
           Using COBRA-TF and Machine Learning Techniques Based on the NRC/PSU RBHT
           Benchmark

         This is an Open Access Article Open Access Article

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      Authors: Yue Jin, Stephen M. Bajorek, Fan-Bill Cheung
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-07-28T03:56:06Z
      DOI: 10.1080/00295639.2022.2087834
       
  • Reactor Physics Experiment on a Graphite-Moderated Core to Construct
           Integral Experiment Database for HTGR

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      Authors: Shoichiro Okita, Yuji Fukaya, Atsushi Sakon, Tadafumi Sano, Yoshiyuki Takahashi, Hironobu Unesaki
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-07-07T03:42:05Z
      DOI: 10.1080/00295639.2022.2087836
       
  • Pressure Drop in Seven-Pin Wire-Wrapped Rod Bundle for the Sodium
           Cartridge Loop in Versatile Test Reactor

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      Authors: Zhengting Quan, Adam Dix, Ran Kong, Seungjin Kim, Mamoru Ishii, Mitchell T. Farmer
      Pages: 1 - 17
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-07-05T07:02:39Z
      DOI: 10.1080/00295639.2022.2082232
       
  • A Critical Review of Heat Pipe Experiments in Nuclear Energy Applications

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      Authors: Scott Wahlquist, Joshua Hansel, Piyush Sabharwall, Amir Ali
      Pages: 1 - 34
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-07-05T06:58:39Z
      DOI: 10.1080/00295639.2022.2082230
       
  • The Legendre Polynomial Axial Expansion Method

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      Authors: Nicholas F. Herring, Benjamin S. Collins, Thomas J. Downar, Aaron M. Graham
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-07-05T06:57:42Z
      DOI: 10.1080/00295639.2022.2082231
       
  • Asymptotic Diffusion Limits of the Multigroup Neutron Transport Equations

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      Authors: Edward W. Larsen
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-06-27T05:07:24Z
      DOI: 10.1080/00295639.2022.2058847
       
  • Frequency Transform Method for Transient Analysis of Nuclear Reactors in
           Monte Carlo

         This is an Open Access Article Open Access Article

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      Authors: Miriam A. Kreher, Samuel Shaner, Benoit Forget, Kord Smith
      Pages: 1 - 12
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-06-10T02:30:18Z
      DOI: 10.1080/00295639.2022.2067739
       
  • Toward a More Realistic Analysis of Neutron Clustering

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      Authors: Thomas M. Sutton
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-05-20T03:40:31Z
      DOI: 10.1080/00295639.2022.2065872
       
  • Spatially Dependent Resonance Self-Shielding in CASMO5

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      Authors: Rodolfo M. Ferrer, Joshua M. Hykes
      Pages: 1 - 18
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-05-06T07:58:11Z
      DOI: 10.1080/00295639.2022.2053491
       
  • Flow-Induced Vibration of Solitary Wire-Wrapped Cylinders in Axial Flow
         This is an Open Access Article Open Access Article

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      Authors: Chad A. Nixon, Wade R. Marcum
      Pages: 1 - 25
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-04-29T03:41:06Z
      DOI: 10.1080/00295639.2022.2058846
       
  • Theoretical Derivation of a Unique Combination Number Hidden in the
           Higher-Order Neutron Correlation Factors Using the Pál-Bell Equation

         This is an Open Access Article Open Access Article

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      Authors: Tomohiro Endo, Fuga Nishioka, Akio Yamamoto, Kenichi Watanabe, Cheol Ho Pyeon
      Pages: 1 - 13
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      Citation: Nuclear Science and Engineering
      PubDate: 2022-04-14T03:11:40Z
      DOI: 10.1080/00295639.2022.2049992
       
 
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